ML20024F060
| ML20024F060 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 08/04/1983 |
| From: | Eddings M, Mason C TENNESSEE VALLEY AUTHORITY |
| To: | NRC OFFICE OF RESOURCE MANAGEMENT (ORM) |
| References | |
| NUDOCS 8309080167 | |
| Download: ML20024F060 (21) | |
Text
~ ' ~
- . . . - ., ~0' u s b'W TENNESSEE VALLEY. AUTHORITY Sequoyah Nuclear Plant P. O. Box 2000 Soddy-Daisy,-Tennessee 37379 AUS I 51983'-
Nuclear Regulatory Commission
.0ffice of Management Information
.and Program Control Washington,-DC 20555 Gentlemen:
Enclosed is'the July 1983 Monthly' Operating Report to the NRC for Sequoyah Nuclear Plant.
Very truly yours,.
TENNESSEE VALLEY AUTHORITY C.'C. Mason Power Plant Superintendent Enclosure cc (Enclosure):
Director, Region II Director, Office of Management Director, Office of Management .Information and Program Control Nuclear Regulatory Commission ' Nuclear Regulatory Commission 101 Marietta Street. Washington, DC 20555 (2 copies)
Suite 3100:
Atlanta, GA '30303 (1 copy) INPO Records Center Suite 1500 L Director, ~0ffice of Inspection 1100 Circle 75 Parkway
_and Enforcement Atlanta, GA ~ 30339 (1 copy) l Nuclear Regulatory Commission l Washington,;DC 20555 (10 copies)
L I- 'Mr. A. Rubio, Director
'Mr.' Bill'Lavallee, NSAC-Electric Power Research Institute
! ' P.'O. Box.10412
~ Palo Alto, CA 94304 (1_ copy)
- Mr. R. C. Goodspeed MNC 461 l
Westinghouse Electric Corporation L' -P. 0.' Box 355 I Pittsburgh, PA - 15230_(1 copy)
~
8309000167 830804 PDR ADOCK 05000327
[
( R PDR -
An Equal Opportunity Employer
e TENNESSEE VALLEY AUTHORITY DIVISION OF NUCLEAR POWER SEQUOYAH NUCLEAR PLANT MONTHLY OPERATING REPORT TO THE NUCLEAR REGULATORY COMMISSION JULY 1, 1983 - JULY 31, 1983 UNIT 1 DOCKET NUMBER 50-327 LICENSE NUMBER DPR-77 UNIT 2 DOCKET NUMBER 50-328
-LICENSE NUMBER DPR-79 Submitted By: M Power Plant Superintendent l
TABLE OF CONTENTS Ope ra tions Summa ry . . . . . . . . . . . . . . . . . . . . . . 1 Significant Operational Events . . . . . . . . . . . . . . . . 1-3 PORV's and Safety Valves Summary . . . . . . . . . . . . . . . 4 Licensee Events and Special Reports . . . . . . . . . . . . . 4-6 Offsite Dose Calculation Manual Changes ........... 6 Operating Data
-Unit 1 . . . . . . . . . . . . . . . . . . . . . . . . . 7-9 Unit 2: . . . . . . . . . . . . . . . . . . . . . . . . . 10-12 Plant-Maintenance Summary . . . . . . . . . . . . . . . . . . 13-18 i.
i-
Operations Summary July, 1983 The following summary describes the significant operational activities for the month of July.- In support of this summary, a chronological log of significant events is included in this report.
Unit 1 Unit I was critical for 730.73 hours8.449074e-4 days <br />0.0203 hours <br />1.207011e-4 weeks <br />2.77765e-5 months <br />, produced 804,010 MWH (gross),
resulting in an average hourly gross load of 1,111,253 kW during the month.
There are 113.07 full power days estimated remaining until the end of cycle
- 2 fuel. With a capacity factor of 85 percent, the target E0C exposure would be reached December 12, 1983. The capacity factor for the month was 91.3 percent.
There was one reactor scram, no manual shutdowns, and no power reductions during July.
j Unit 2 Unit 2 was critical for 420.55 hours6.365741e-4 days <br />0.0153 hours <br />9.093915e-5 weeks <br />2.09275e-5 months <br />, produced 481,030 MWH (gross),
resulting in an average hourly gross load of. 1,143,812 kW during the month.
The refueling' outage began on July 19, 1983. The capacity factor for the month was 55.6 percent.
There was one reactor scram, no manual shutdowns, and no power reduction during July.
I Significant Operational Events 4
Unit 1 Date Time Event 07/01/83 0001 . Reactor in mode 1 at 100% power pro-ducing 1165 MWe.
07/11/83 1519 A low EHC tank level indication tripped the turbine and reactor. The low indication was due to a faulty switch.
07/12/83 0435 The reactor was taken critical.
0615 Reactor at 10% and rolling the
. turbine.
0620 Turbine tripped due to loss of vacuum (unit was not on-line).
T
,,, , - ~ . ......-..n.. ,
,,y .,w. ,,,,-,-m-- , - . ,--,g.- , , , , , , .-
1 h .
Significant Operational Events I Unit 1 (Continued) l Date Time Event l 07/12/83 0920 Turbine tripped due to loss of vacuum !
(unit was not on-line). I 1120 Rolled the turbine.
1148 The unit was tied.on-line.
'1410 Reactor at 30% power producing 238 We and holding due to steam genera tr.: water chemistry requirements.
07/13/83 1310 Began power ascension.
07/14/83 0451 Reactor at 100% producing 1150 We.
07/16/83 0400 Reactor at 90%, water box 1A-2 out of service for tube leak testing.
07/17/83 1039 Reactor at 100% power producing 1160 We. Water box tube leak testing completed.
07/31/83 2359 Reactor in Mode 1 at 100% producing 1155 We.
Unit 2 Date Time Event 07/01/83 0001 Reactor in Mode 1 at 98% power producing 1160 We. #3 governor valve'is fully closed and control ;
rod D-8 is inoperable.
07/18/83 1233 MFPT 2B tripped causing a turbine runback. The reactor could not track the runback because the control rod drives were in manual--thus the reactor tripped. This trip. ended a record setting. continuous run of 195 days-9 hours and 34 minutes.
- 07/19/83 0215 #3 steam generator tube leak was calculated to be 553 gallons per day.
Significant Operational Events Unit 2 (Continued)
Date Time Event i
07/19/83 0330 The refueling / modification outage began.
1 2114 Reactor entered Mode 4.
07/20/83 0758 Reactor entered Mode 5.
-07/31/83 2359 Reactor in Mode 5 and the refueling /
modification outage continues.
l l
i l
l i
l
. - - _ _ _ _ - - _ _ _ _ _ - _ - _ - _ _ _ _ _ - _ _ _ _ - - - _ - - _ _ _ - - _ _ _ - - - _ _ _ _ _ - _ - _ - - - - - - - - - - - - - - .-l
~
PORV'S and Safety Valves Sunnary No PORV's or safety valves were challenged during the month.
Licensee Events and Special Reports The following Licensee Event Reports (LER's) were sent during July 1983, to the Assistant Director of Nuclear Power (Operations) for reporting to the Nuclear Regulatory Commission.
Unit 1 LER SUBJECT SQR0-50-327/83088 During the performance of STEAR 83-07, the #3
- i. steam generator AFW inlet valve 1-LCV-3-148A hand switch did not work. The handswitch internal operator and ramp position were found to be stripped resulting in the loss of manual control-of the valve.
SQRO-50-327/83090 During the performance of SMI-1-SD1B-5 the 6900 volt shutdown board 1B-B was deenergized for approximately 52 seconds. Personnel failed to -
reset device 86518 before replacing the Rx-trip cutout blocks as required in the procedure.
SQRO-50-327/83091 Containment vacuum relief valve 1-30-571 was declared inoperable when containment vacuum relief isolation valve 1-FCV-30-46 was discovered failed closed.
SQRO-50-327/83092 The P250 process computer failed causing the subcooling margin monitor to be inoperable at 1340 hrs on 07/11/83 and at 0400 hrs on 07/08/83.
The 07/11/83 event was' caused by a blown fuse at the progra;amers console and local control was lost
- but the computer was not affected. The 07/08/83 was caused by an interrupt overload from SSPS causing the watchdog timer to time out.
SQRO-50-327/83094 Steam generator #4 steam flow indicator 1-FI-1-28A
' indicated'zero. 1-FI-1-28B indicated 10E6 lbs/hr.
Since the indicator failed, low air was suspected in the sense lines and they were back filled and proper output was verified.
.SQRO-50-327/83096 The gaseous effluent radiation monitor for the Auxiliary Building exhaust 0-RM-90-101 was declared inoperable due to loss of flow to the iodine sampler. Investigation revealed a stopped up charcoal filter.
Licensee Events and Special Reports Unit 1 LER SUBJECT SQR0-50-327/83098 Glycol containment isolation valve 1-FCV-61-191 was discovered failed closed due to a ruptured diaphragm.
SQRO-50-327/83100 Automatic control valve 1-PCV-3-122 for train A AFW was delcared inoperable when it failed to open after a reactor trip. An investigation revealed the local manual control switch had been left in the closed position.
Unit 2 LER SUBJECT SQR0-50-328/83087 While reducing power for maintenance purposes, the axial flux difference was discovered outside the plus or minus 5% target band.
SQR0-50-328/83089 Steam generator pressure channel 2-PI-1-1C for the remote shutdown instrumentation was declared inoperable due to failing high. The failure was caused by a bad transistor in the GE model 5500 module.
SQRO-50-328/83093 The condenser vacuum flow rate monitor 2-FT-2-257 was declared inoperable when it failed to indicate the flow rate. Condensation in the sense lines is thought to be the probable cause.
SQRO-50-328/83095 The plant process computer failed three times rendering the subcooling margin inoperable:
07/08/83 '1325 A power glitch stopped the computer.
07/13/83 0045 A dirty edge connector on the memory module.
07/13/83 0140 A loose connection on the memory module.
SQR0-50-328/83097 Containment sump level channel 2-L-63-176 was declared inoperable due to reading high. The cause appears to be air bubbles in the reference leg. The investigation continues.
Licensee Events and Special Reports ~
-Unit 2 (Continued) *
- -LER SUBJEC_T SQR0-50-328/83099 During ther performance of SI-111, five main
. steam line safety valves, 2-1-512, -513, -517,
-519, and -521 were found with lift setpoints out of tolerance. The 6 X 10 Crosby valves were _from 0.2 to 0.8 percent out of tolerance caused by againg of. valve springs and ambient-temperature variation.
Special Reports There was one special report transmitted during the month of July.
83 Fire-Barrier Penetration Breached Offsite Dose Calculation Manual Changes
_There were no changes to the Sequoyah Nuclear' Plant ODCM during the month.
_. r CFECATING DATA FEFORT CCCKET AC. SC-327 CATE AlGLST 4 19E3
'CCFFLETEC SY F. G. ECCINGS I TELEFFCNE (c15) E7C-c196 CFERATIhG STATUS
- 1. UNIT AAME: SECUOYAH StCLEAR FLANT, UNIT '1 ACTES:
- 12. REFORT FEFICC: JCLY 1 JLLY 31 1953
- 3. LICEASED 1 F E R M. A L . F C L E F ( F k T ) : 3411.C
- 4. NAMEFLATE SATING (GRCSS FLE): 122C.6 5.1DESIGh ELECTRICAL RATING (NET MLE): 114E.0 --
~ -
- 6. NAXIMLM CEFEhDASLE CAFACITY (GROSS FWE): 1153.C '
- 7. MAXIPLM CEFEhDABLE CAFACITY (hET FWE): 114E.C
- 8. IF. CHANGES OCCUR IN CAFACITY FATINGSCITEFS NLPEERS 1
3 THRCUGE 7)SIhCE LAST REF0GT, GIVE.REASchS: _________.. '
..__.___...________.........____________.____.4..___....
-9. FCWER LEVEL TC LEICH FESTFICTEDrIF Ah Y (hET Mbi):_ ____..
10.'REASch5 FCF RESTRICTICNSrIF ANY:a ...... _____. ______. '
~
~
/ % e THIS-FCNTh YR.-TC-DATE C OMLL A T;I\ E i
11.'HCURS IN FEPCRTING PEFICC L74'.CC '
SC17.CC , 15264.C0
- 12. huMBER OF FCLRS FEACTCs LAS CFITICAL- 7?C.73 4529.41 12C65.11
C.CC
- 14. HCURS GEhERATCR Ch-LIFE '
72I.5C 44?5.2C 11758.70
- 15. UhIT FESEFtE-SHUTCCWN HCU:S C.CC- 1 'C'.CC C .' C C
- 16. GFCSS THEFFAL ENEF GY 'G ENER ATEC (PkF) 2376192.61 144541C1'.99- 3?766843.99
- 18. AET-ELECTFICAL ENERGY GENERATED (FWh) 775099.CC 4 7 9 8 9 5 c . C,C 122349eG.C0 j
- 19. UhIT SERVICE FACTCR 97.24 E7.i7 64.32
'20.-Lh1T AVAILABILITY FACTCF c -97.24 67.27 64.38
- 21. thITfCAPACIT) FACTCR(LSIhG FCC NET) SC.75 32.12 S E '. 3 5 .
22.lUhlT C A F A C I T i F A C T O F (L EI h'G D3G. NET) 9C.75 62.18 58.35 -
- 23. UAITEFCRCEC-CUTAGE' Rale 2.76 3.97 '13 . C 9 s
- 24. ShuTCCwh5-SCFEDULED CVEF-HEX,1Le J0hTHS ( T ) F;E , DATE, AhD CLFATION CF EACH):
R_e_f_uel_i.ng./m.o.d.i.f.ica_t_i.o.n. .(c.yc.le.2_) ou_ t_a_ge.'_ t.o. .s.t_ar_t. _De_ce.m_b_e r 2, 1983 for 77 days.
'25. IF ShLTDChh AT EhD CF REFCRT FERICD, ESTINATEC DATE CF STAFTLP: -
____________________.......'......______ ______.___..._________.__ ^
'/
.hCTE-TEAT TFE THE iR.-1C-DATEt.8'NC 5 CUMULATIVE'kALUES FAVE SEEh UFCATEC. '
o
- \
^
l 9 A =
w i
I %
__ _ _ _ . _ __ A . _ . , _ . _ , _ . _
. ', \ -
's -
e k
.g.
~
f .
AVERAGE DAILY UNIT POWER LEVEL
- (
'~
DOCKET NO. 50-327 UNIT ONE DATE August 3, 1983 i , COMPLETED BY M. Eddings i"
TELEPHONE (615) 870-6196 MONIH , '- JULY
\
DAY AVERAGE DAILY POWER LEVEL DAY
' AVERAGE DAILY POWER LEVEL (MWe-Net) (gwe. Net) 1 1122 17 1080 2 1124 18 1111 3 1121 '
19 1112 4 1123 20 1114
~
5 1121 21 'T 1112 6 '1119 22 IllD?
7 1119 23 1112 8 1110 1119 24 9 1119 25 1099
^ 10 1118 1 26 1107 11 708 27 1108 1110 12 ,
309 -
28 13 480 29 1111 14, 1101- 30 1111
- -, 15' -1'108 ' 31 1110
' AJ -
16 Id35 .
l'
_;' ,, \
4
- INSTRUCTIONS On t is'f6rmat, list the average daily unit power level in MWe-Net for each day in 3.the? reporting month.
Compute to the nearest whole megawatt.
.2 (9/77)
, 6- ..' ,
a -
- a G
.l'
,' - v -
- 1
' UNIT SHUTDOWNS AND POWER REDUCTIONS' , . DOCKET NO. 50-327 -
UNIT NAME seouovah one
/. DATE August 3, 1983 COMPLETED BY M. c. Eddings JUIX REPORT HONTH TELEPHONE (615) 870-6196 4 .
W 1O
- g7 "e c [t Licensee y Cause & Corrective No. -Da te -
' 8, O$ @ '8 0 $ Event $*. gao Action to y 2j g 5y* Report ! "~3 g,7 Prevent Recurrence
$" EN5 A N" "
8*
2
/
20 830711 F 20.5 A 3 Reactor tripped due to a low tank level
- switch on the E.H.C. tank.
1 2 3 4 F: Forced Reason: Method: Exhibit G-Instructions S: Scheduled A-Equipment Failure (E.iplain) 1-Manual for Preparation of Data B-Maintenance or Test 2-Manual Scram. Entry Sheets for Licensee C-Refueling 3-Automatic Scram. Event Report (LER) File (NUREG-D-Regulatory Restriction 4-Cont. of Existing 0161)
- E-Operator Training & License Examination Outage
'F-Administrative 5-Reduction
' G-Operational Error (Explain) 9-Other. 5 (9/77) H-Other (Explain) Exhibit I-Same Source
CFEcATING DATA FEDCET CCC<iT NC. SC-325 CATE i-4-53 (CVELETEC EY C.C.CUPREE TELEFhCNE o7C-0543 CFERATIhG STATUS
- 1. LhIT hAPE: SE0LOYAF NLCLEAR FLANT, UNIT 2 NCTES:
- 2. REF0FT PEFICC: JCLY 1-31r1453
- 3. LICEhSEC TFE6 MAL FC.EF(5.T): 3411.C
- 4. NAMEFLATE FATING (sFC!S *LE): 122C.c
- 5. DESIGA ELECTFICAL RATING (NET MnE): 114f.C
- 6. PAXIPLM DEFEh0ASLE CAFACITY (G;Ca5 v aE): 11e3.C
- 7. FAXIPLM CEFEhDASLE CAFACITY (NET .E): 1126.C
- 2. IF CFAhCc5 CCCUR IN CAPACITY FATINGS(ITEP3 NLSOEFS 3 THFCLGP 7)SIhCE LAll CEFC:1, CIkE 4EASChS:............
9 FCWLR LEkEL TC .FICW FESTFICIEurIF ANY(NET v sE): .__,,__
- 10. REASCh3 FCA FESTRICTICNS,IF ANY:,,,,__............ ___.
TFIS PCNTF Y:.-TC-CATE CLNLLATItE
- 12. ALMEEF CF FCLRS GEACTCH .A3 CFITICAL 4 2C .5 5 475C.77 E63G.47
- 14. FCURS GEhEFATCF C h-L D E aiC.55 4715.95 E522.70
- 16. GECSS THEFPAL ENEFGy CENE;ATEC (FWM) 1415C3C.44 15401769.43 2755c3eC.23
- 19. U N IT SERVICE FACTCc 56.53 92.71 53.2e 2C. LNIT AVAILABILITY FACTC9 56.53 92.71 93.36
- 21. UNIT CAPACITY FACTC-(LSIhG FCC NET) 55.17 29.11 75.36
- 22. UNIT CAPACITY FACTCR(LSING CE: NET) 54.21 67.55 77.C1
- 23. LhIT FCACEC CLTASE 4 ATE 1.c4 1.14 E.E4
Seto4v.9..OB3__ ......__________............................___ .
hCTE TFAT TFE THE )R.-TC-DATE ANC CUPULATIVE VALUES FAVE :EEN UFCATED.
t
\.
AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-328 UNIT TWO DATE August 8, 1983 COMPLETED BY D. C. Dupree l TELEPHONE (615) 870-6543 MONTH JULY l
DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (HWe-Net) 1 1144 17 1091 2 1114 18 568 3 1115 19 Refueling Outage 4 1116 20 Refueling Outage 5 1114 21 'T Refueling Outage 6 1110 22 Refuhling Outage 7 1110 23 Refueling Outage 8 947 24 Refueling Outage 9 1112 25 Refueling Outage 10 1112 26 Refuelirg Outage 11 1112 27 Refueling Outage 12 1102 28 Refueling Outage 13 1061 29 Refueling Outiage 14 1094 30 Refueling Outage 15 1086 31 Refueling Outage 16 1094 INSTRUCTIONS On this format, list the average daily unit power level in HWe-Net for each day in the reporting month. Compute to the nearest whole megawatt.
(9/77)
UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-328
- UNIT NAME Sequoyah Two DATE August 8, 1983 COMPLETED BY D. C. Dupree REPORT MONTH JULY TELEPHONE (615) 870-6543 4.
1C gg e4, c yy Licensee y Cause & Corrective No. Date 2, O ); jj @
p
@ Event $$ 8% Action to 2e
- 2 5y* Report !! g] 2, ? Prevent Recurrence E" E55 N" 5" E "
11 830718 F .7. A 3 "B" M.F.P. tripped causing a unit rur.back "A" M.F.P. could not maintain the unit. This in turned caused a unit trip.
12 830718 S 7.95 B 9 Rod drop test. (reactor was in mode #3) 13 830719 S 308.50 C 9 Refueling outage (reactor was in made #3) 1 2 3 4 F: Forced Reason: Method:
S: Scheduled A-Equipment Failure (Explain) Exhibit G-Instructions 1-Manual for Preparation of Data B-Maintenance or Test 2-Manual Scram. Entry Sheets for Licensee C-Refueling 3-Automatic Scram.
D-Regulatory Restriction Event Report (LER) File (NUREG-4-Cont. of Existing 0161)
E-Operator Training & License Examination Outage F-Administrative 5-Reduction G-Operational Error (Explain) 9-Other 5 (9/77) H-Other (Explain)
Exhibit I-Same Source i
Plant Maintenance Summary The following significant maintenance items were completed during the month of July 1983:
MECHANICAL MAINTENANCE
- 1. Replaced the head gasket on auxiliary air compressor A-A.
- 2. Performed the annual surveillance on diesel generator 2A-A per SI-102.
- 4. Disassembled, inspected, cleaned, relubricated and replaced the coupling to solve the vibration problem on the containment spray pump lb-B.
- 5. Replaced the purge paper in ice condenser floor drains following the unit 1 trip on July 11, 1983.
- 6. Disassembled, inspected and lubricated the reactor cavity side and spent fuel pit side upender bearings.
- 7. Repaired the CRDM unlatching tools in preparation for the unit 2 refueling outage. Also repaired the spent fuel pit to transfer canal gate seal leak.
Electrical Maintenance
- 1. Continued the installation of dimension 2000 phone system.
- 2. Continued the sytematic walkdown and inspection of the E-field.
- 3. Continued the six year inspection of the switch yard breakers (PCB's and MOD's).
- 4. Began inspection of all shop and plant cranes.
- 5. Numbered the doors on inside of ice condenser.
- 6. Started the reactor coolant pump modifications on pumps 1 & 4 (unit 2).
- 7. Relamped unit 2 containment.
- 8. Labled the phones in unit 2 containment.
- 9. Repaired control rod D-8 lift coil.
- 10. Removed and shipped the No. 3 heater drain pump motors for modification.
- 11. Started the 6900 and 480 volt motor insulation resistance testing.
- 12. Started the containment motor lead inspection.
Plant Maintenance Summary (Continued)
Instrument Maintenance None reported at this time.
Field Services Group
- 1. ECNs 2780/5200--Post-Accident Sampling Facility (Units 1 and 2)
The installation of the IIVAC duct and equipment for the PASF area is continuing. Component cooling piping to the PASF coolers on unit 2 is complete and piping tie-in is in progress. Work is in progress in accumulator room #4 to install the unit 2 post-a-cident sample tubing.
All work in unit 2 annulus is complete, except for the solenoid valves.
Material for the steel containment vessel penetration plates is here, and fabrication is complete. Steel containment penetrations will be made on unit 2 after core alterations.
Lower containment - Conduit installation is in progess in all areas of lower containment as well as extensive scaffold erection.
Ice Condenser - All 35 conduit and junction box hangers were completed.
Conduit installation is in progress.
Upper Containment - Conduit installation in upper containment has been in work since prior to the unit outage and is nearing completion.
Completion of conduit installation in this area is impacted by use of the polar crane for RPV head disassembly.
Reactor Cavity - Work in this area is not expected to begin until after refueling operations are complete.
- 3. ENC 5009--ERCW Piping Changeout (Units 1 and 2)
Work on the unit 2 "A" train penetration room coolers, and the hypochlorite piping serving the units 1 and 2 containment spray heat exchanger has been completed.
- 4. ECN 5645--Steam Generator Blowdown (SGBD) Heat Exchangers Hanger design information has been received and work is continuing on hanger installation. Installation of instrumentation has been delayed because of the lack of sufficient design information. The heat exchangers for unit 2 have been installed. Fabrication and installation is continuing on unit 2 el. 662 & 685.
Plant Maintenance Summary (Continued)
Field Services (continued)
- 5. ECN 5495--Fi a Office Building Power Supply Installation of the Harris computer terminal is complete. The evacuation alarm installation has been completed. Miscellaneous cables were installed and some communication cables remain.
- 6. ECN 5106--Reactor Vessel Level Indication System (Units 1 and 2)
Twelve conduit are left to be installed and two cables on El. 685 remain to be pulled. The remaining work must be worked during the outage.
- 7. ECN 5237--Laundry Room Improvements The laundry room ventilation hood was prefabbed. Conduit and power cable installation continued up to the beginning of unit 2 cycle 1 outage.
- 8. ECN 5596--Install Batch Neutralization Tank All valves have been received and piping and hanger installation is continuing. Tie-in to the existing system has been made, but is not operable. Some instrumentation and the major portion of electrical work remain to be done. The system is scheduled for interim operation by September 1.
The installation of TSC power equipment, power supplies, and pulling of TSC power cables in in progress. TSC equipment is being readied for the site acceptance test. Work on fire detection system is continuing.
- 10. ECN 5642/5582--Add N,, Regulating Station To Supply N,, To Deaeration Distribution System Inside Condensate Storage Tanks /& To Steam Generators Piping is complete for both ECNs 5642/5582 to the nitrogen supply station except for one pressure regulator valve to be installed. Minor modifications to the valve cabinets and miscellaneous painting remain to be done.
- 11. ECN 2773--Install Radiation Detectors (Unit 2)
Preparation of the main control room panels 2-M-30 and 2-M-31 is continuing.
Actual installation of the panels is in progress.
- 12. ECN 5519--Plant Crane Escape Devices Sandblasting and painting of the members are to be completed during the respective units cutage. All other work is complete.
Plant Maintenance Summary (Continued)
Field Services (continued)
- 13. ECN 5449--6.9-kV Shutdown Board Degraded Voltage Circuitry Internal panel wiring is continuing for the following panels: 6.9-kV shutdown boards, 6.9-kV logic panels, main control room communication panel 1-M-21, and the auxiliary control room annunciation panel 0-L-4.
- 14. ECN 5867--Fuel Transfer System No work done in July.
- 15. L-DCR 1847--Chemical Feed Injection to Condensate Polisher Discharge All hangers have been installed and tubing installation is complete.
Tie-in of the chemical feed system to the condensate polisher discharge piping has not been completed. System tie-ins can be made during unit 2 cycle 1 outage.
- 16. L-DCR 1883--Liquid Nitrogen Station The high pressure portion of the nitrogen system is operational. The low pressure portion of the system is complete, except for a temperature isolation valve that is to be installed by the vendor.
- 17. ECN 5684--RCP Motor Oil Spray Shields Prefabrication work continued and work is in progress to install RCPM No. 3 spray shield frame. Fabrication of the sheetmetal cover is now in progress.
- 18. ECN 5644--Hotwell Makeup and Dumpback No work done.
19 ECN 5847--Plant Fire Dampers This ECN authorizes changeout or modification of several fire dampers located throughout the plant. Installation of the negator spring assemblies and post-modification testing of the dampers is 53% complete.
Platform installation for both units 1 & 2 is 80% complete. All that remains is the mounting gates and painting. Work has been delayed because of material unavail.bility (hinges).
- 21. L-DCR-1822--Condensate Sources To Secondary Chemical Feed System All that remains to complete this modification are the piping tie-ins when require a system outage.
Plant Maintenance Summary (Continued)
Field Services _(continued)
- 22. ECN 5870--Auxiliary Building Drain To Turbine Building Sump Installation of piping was completed with the exception of three hangers. Two hangers require FCR and variance. Scaffolding had to be removed from the 690 El. dress out area. Painting of hangers remains to be completed.
- 23. L-DCR-1930--Secondary System Sample Sinks The sample sinks for secondary side sampling of contaminated water in the condensate demineralizer building have been completed.
- 24. ECN 5468--Install Security Grills The installation of a locking device on the hatch in the waste packaging area was completed per a FCR to the security barrier vent MOD workplan.
The ECN is now complete.
- 25. ECN 5647--Unit 2 Main Feed Pump Turbine (MFPT) Condenser Air Removal Piping
.This modification splits the existing MFPTC common air removal piping into two separate headers and routes to the common vacuum pump suction header. Fabrication and installation of hanger base plates is in progress on condense A. Piping prefabrication is also in progress.
- 26. ECN 5841--Temporary Hot Tool Room Field Services ' worked in conjunction with construction to complete facilities for unit 2 cycle 1 outage use. The HEPA filter system was made operable. The sand blast room and hot lathe room were tied into to the HEPA filter system. Installation of shelves were complete and tools moved in.
- 27. ECN 5608--Pressurizer Manway Core drilling for'the pressurizer enclosure manway was completed.
- 28. ECN 5856--Pressurizer Loop Seal Drain Work is under way to make the necessary changes to the existing pipe supports. Fabrication of new supports is~in progress.
Began jobsite preparations of the pressurizer ~ enclosure area for
-removal of the PORV's and reroute of the drain piping. Work is progressing'to disassemble the valves for removal.
I
Plant Maintenance Summary (Continued)
Field Services (continued)
- 30. ECN 5743--Pressurizer Enclosure Flatform Completed writting the workplan and the initial fabrication of the platform began.